CN115376713B - Integrated reactor loading and reloading device, system and process - Google Patents
Integrated reactor loading and reloading device, system and process Download PDFInfo
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- CN115376713B CN115376713B CN202210939550.4A CN202210939550A CN115376713B CN 115376713 B CN115376713 B CN 115376713B CN 202210939550 A CN202210939550 A CN 202210939550A CN 115376713 B CN115376713 B CN 115376713B
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- 238000000034 method Methods 0.000 title claims abstract description 26
- 230000008569 process Effects 0.000 title claims abstract description 23
- 239000003758 nuclear fuel Substances 0.000 claims abstract description 24
- 239000000446 fuel Substances 0.000 claims description 27
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 20
- 239000000463 material Substances 0.000 claims description 18
- 230000007246 mechanism Effects 0.000 claims description 11
- 239000002915 spent fuel radioactive waste Substances 0.000 claims description 11
- 238000005259 measurement Methods 0.000 claims description 4
- 238000007789 sealing Methods 0.000 claims description 4
- 238000012546 transfer Methods 0.000 claims description 4
- 238000012423 maintenance Methods 0.000 abstract description 6
- 230000009286 beneficial effect Effects 0.000 abstract description 3
- 238000004904 shortening Methods 0.000 abstract 1
- 230000000712 assembly Effects 0.000 description 9
- 238000000429 assembly Methods 0.000 description 9
- 239000000306 component Substances 0.000 description 7
- 238000001363 water suppression through gradient tailored excitation Methods 0.000 description 6
- 238000005516 engineering process Methods 0.000 description 5
- 230000000149 penetrating effect Effects 0.000 description 3
- 230000004048 modification Effects 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 229910000831 Steel Inorganic materials 0.000 description 1
- 230000008901 benefit Effects 0.000 description 1
- 230000008859 change Effects 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 239000008358 core component Substances 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000013461 design Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000006872 improvement Effects 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 210000001503 joint Anatomy 0.000 description 1
- 238000005457 optimization Methods 0.000 description 1
- 230000008439 repair process Effects 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
- 230000007704 transition Effects 0.000 description 1
Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
- G21C19/207—Assembling, maintenance or repair of reactor components
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/02—Details of handling arrangements
- G21C19/06—Magazines for holding fuel elements or control elements
- G21C19/07—Storage racks; Storage pools
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/02—Details of handling arrangements
- G21C19/10—Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Carriers, Traveling Bodies, And Overhead Traveling Cranes (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses an integrated reactor refueling device, system and process, wherein the device comprises a containment, a reactor pressure vessel, an integrated upper hoisting structure, a reactor core hoisting device, a reactor core guiding device and the like, wherein the upper containment and the upper reactor pressure vessel form the integrated upper hoisting structure to be integrally uncapped, and the integral hoisting based on the reactor core is adopted to carry out the extrareactor refueling. The reactor core guiding device with the two-stage guiding structure is used for realizing the reactor core refueling operation of the bottom of the integrated reactor pressure vessel in a narrow space, simplifying the reactor refueling process, shortening the refueling key path, providing a preferable and practicable refueling method, and being beneficial to the reduction of the height of the operation and maintenance factory buildings of the nuclear power plant and the adoption of multi-stack modularized layout of the nuclear power plant.
Description
Technical Field
The invention belongs to the technical field of operation and maintenance of nuclear power plants, and particularly relates to an integrated reactor loading and reloading device, system and process.
Background
The disclosure of this background section is only intended to increase the understanding of the general background of the invention and is not necessarily to be construed as an admission or any form of suggestion that this information forms the prior art already known to those of ordinary skill in the art.
The reactor loading and reloading system is a system for systematically solving the problems of disassembly of a reactor body, replacement of reactor core fuel and transportation and storage of fuel.
In the prior art, a compact pressurized water reactor refueling system comprising an integrated reactor generally adopts a mode of sequentially uncovering and then carrying out in-reactor refueling, namely sequentially removing a containment top cover and a reactor pressure vessel top cover, sequentially lifting out a control rod driving mechanism, an upper in-reactor component and an in-reactor measurement grid, and sequentially carrying out the replacement operation of a single fuel assembly in the reactor. The method mainly comprises the following steps of firstly, using a loading and unloading machine with a gantry crane structure to run above a reactor, descending a fuel gripping device to the top of a fuel assembly, abutting and gripping and locking the gripping device through a structure of a gripping device mechanism and a fuel assembly upper tube seat, lifting the gripping device and carrying the fuel assembly to remove a reactor core and transfer the fuel assembly to a spent pool, thereby completing the removal operation of one fuel assembly, and circularly carrying out the removal of the next fuel assembly until the complete removal of the reactor core. The loading of the core is the same as the process and the sequence is reversed.
The existing material-changing technology has the following defects:
in the first aspect, as a mode of carrying out in-pile refueling after uncovering in sequence is adopted, all steps of reactor disassembly and refueling carried out in sequence cannot be carried out in parallel, and a refueling key path is longer;
In the second aspect, for an integrated reactor, due to the highly compact fully built-in layout, the containment and the reactor pressure vessel are provided with complex reactor top penetrating members, and a compact built-in control rod driving mechanism and a heat exchange assembly are arranged in the reactor, so that the moving and telescopic space of a loading and unloading machine sleeve in the reactor when the traditional material changing technology is adopted is greatly restricted, and great difficulty is brought to the accessibility of the components in the reactor core;
In the third aspect, for the integrated reactor, the space in the reactor after the material changing and uncapping is compact and narrow, and further, based on the requirement of establishing natural circulation, the depth of the reactor core is greatly increased relative to that of a forced circulation pressurized water reactor, and the operation of replacing the reactor core faces the deep-well ultra-deep reactor core operation, so that the in-reactor observation and grabbing necessary for the operation of the fuel in the reactor core by the traditional material changing technology are greatly restricted;
In the fourth aspect, the integrated reactor has the characteristics of high miniaturization and compactness, is convenient for flexibly adopting the modularized layout in the power plant arrangement, and adopts the existing material changing technology to need more disassembly storage positions and process spaces, so that the advantage exertion of the integrated reactor in the aspect of the modularized layout of the reactor is limited.
Disclosure of Invention
Aiming at the problems in the prior art, the invention aims to provide an integrated reactor loading and reloading device, an integrated reactor loading and reloading system and an integrated reactor loading and reloading process, which overcome the difficulty and complexity of the integrated reactor adopting a high-integration structure in terms of the operation of the reactor loading and reloading process and the fuel of a deep reactor core by adopting an integrated loading and reloading mode, provide a reasonably simplified reloading process to realize feasible reloading implementation, shorten a major repair critical path and be beneficial to the modularized arrangement of a nuclear power plant adopting the integrated reactor.
In order to solve the technical problems, the method is realized by the following technical scheme:
in a first aspect of the invention, there is provided an integrated reactor refueling apparatus comprising:
the safety shell is provided with a material changing flange, the material changing flange divides the safety shell into an upper safety shell and a lower safety shell, and the top of the upper safety shell is provided with an overhaul flange;
The reactor pressure vessel is provided with a refueling flange which divides the reactor pressure vessel into an upper reactor pressure vessel and a lower reactor pressure vessel;
The upper containment vessel and the upper pressure vessel are of an integrated structure, and an integrated upper hoisting structure is formed.
In some embodiments of the invention, the refueling flange and the service flange form a two-stage open top structure.
In some embodiments of the invention, the control rod drive mechanism, the upper internals and the in-reactor measurement grids are disposed within the upper reactor pressure vessel, forming an integrated upper reactor pressure vessel.
In some embodiments of the present invention, the lower reactor pressure vessel is internally provided with a core lifting structure, a core hanger and a core guide, the lower end of the core hanger being connected to the core lifting structure.
In some embodiments of the invention, the core guide includes an out-of-stack guide and an in-stack guide.
In a second aspect of the present invention, there is provided an integrated reactor charge-up system comprising said integrated reactor charge-up system, further comprising: integral type reloader, heap chamber sluice gate, spent pool sluice gate, integral type upper portion hoisting structure storage rack, reactor core hoisting structure storage rack, spent fuel storage grillwork and reloading operation hall bridge crane.
In some embodiments of the invention, the integrated refueling machine is a bridge crane with telescoping sleeves and fuel assemblies and an insert-specific operating gripper for replacing the fuel assemblies and inserts in the off-stack and spent pool areas.
In some embodiments of the invention, the stack chamber sluice gate is an automatic sluice gate with a restarting seal and with a mobile switch actuator for isolating the stack chamber from the refueling water sump.
In some embodiments of the invention, the spent pool water gate is an automatic water gate with a restart seal and a flat-open switch actuator for isolating a refueling pool from a spent fuel pool.
In a third aspect of the present invention, there is provided an integrated reactor refueling process implemented using the integrated reactor refueling system, comprising the steps of:
carrying out two-stage topping on the integrated reactor loading and reloading device to realize integrated uncovering, integrally removing the integrated upper hoisting structure, and placing the integrated upper hoisting structure on a storage rack of the integrated upper hoisting structure;
the reactor core lifting device is used for integrally lifting the reactor core lifting structure and is placed on a reactor core lifting structure storage rack;
carrying out off-pile refueling on the reactor by using an integrated refueling machine;
and (5) reloading the reactor with the reloaded reactor according to the reverse steps of the steps.
One or more of the technical schemes of the invention has the following beneficial effects:
1. By adopting the integral hoisting and off-pile refueling modes of the reactor core, compared with the existing pressurized water reactor refueling technology, the operation of the fuel assembly can be decomposed from a refueling key path and is synchronously carried out with the further disassembly of the reactor, so that the overhaul path is shortened, and the operation and maintenance economy of the power plant is improved.
2. Due to the adoption of the integrated upper hoisting structure and the two-stage open-top implementation, the integrated uncovering can be realized, so that the complex penetrating piece disassembly and assembly of the integrated reactor roof and the complex reactor component disassembly process are greatly simplified, the difficulty of changing materials is reduced, the critical path of changing materials and overhauling is shortened, and the operation and maintenance economy of a power plant is improved.
3. By adopting the reactor core guiding device with the two-stage guiding structure, the difficulty in operation and observation of a deep well type ultra-deep reactor core fuel assembly of the integrated reactor can be avoided, and the centering problem of the deep reactor core operation of the integrated reactor can be solved.
4. Due to the adoption of the system structure simplification and optimization brought by the integrated uncapping, the integral hoisting of the reactor core and the off-stack refueling modes, the modular arrangement of compact reactors such as the integrated reactor is facilitated, the overall arrangement of single-stack, double-stack or multi-stack is conveniently realized, and the technical flexibility of the integrated reactor in the aspect of factory site application is improved.
5. Due to the fact that the integral reactor core lifting mode is adopted and the reactor core guiding device with the two-stage guiding structure is matched, the water level of the reactor cavity is lowered when the reactor core lifting device is arranged below, the design height of the reactor core lifting device can be greatly shortened, the process height of an operation and maintenance factory building is greatly reduced, and the construction economy of the pressurized water reactor is improved.
Drawings
The accompanying drawings, which are included to provide a further understanding of the application and are incorporated in and constitute a part of this specification, illustrate embodiments of the application and together with the description serve to explain the application.
FIG. 1 is a schematic view showing the overall structure of an integrated reactor refueling apparatus according to embodiment 1 of the present invention;
fig. 2 is a schematic diagram of a split structure of an integrated reactor refueling apparatus according to embodiment 1 of the present invention;
FIG. 3 is a top view of the integrated reactor refueling system according to embodiment 2 of the present invention;
FIG. 4 is a cross-sectional view of the integrated reactor refueling system according to embodiment 2 of the present invention;
fig. 5 to 12 are schematic views showing the state of the integrated reactor in the process of refueling according to embodiment 3 of the present invention.
In the figure, 1, a containment vessel; 2. a reactor pressure vessel; 3. an integrated upper hoisting structure; 4. a core lifting structure; 5. a core hanger; 6. a core guide; 7. an integral type reloading machine; 8. a pile cavity sluice gate; 9. a spent pool sluice gate; 10. an integrated upper hoisting structure storage rack; 11. a core lifting structure storage rack; 12. a lower in-stack component storage rack; 13. spent fuel storage grillwork; 14. and (5) material changing operation is carried out on the hall bridge crane.
Detailed Description
It should be noted that the following detailed description is illustrative and is intended to provide further explanation of the invention. Unless defined otherwise, all technical and scientific terms used herein have the same meaning as commonly understood by one of ordinary skill in the art to which this invention belongs.
It is noted that the terminology used herein is for the purpose of describing particular embodiments only and is not intended to be limiting of exemplary embodiments according to the present application. As used herein, the singular is also intended to include the plural unless the context clearly indicates otherwise, and furthermore, it is to be understood that the terms "comprises" and/or "comprising" when used in this specification are taken to specify the presence of stated features, steps, operations, devices, components, and/or combinations thereof.
Example 1
As shown in fig. 1 and 2, there is provided an integrated reactor refueling apparatus comprising a containment vessel 1, a reactor pressure vessel 2, an integrated upper lifting structure 3, a core lifting structure 4, a core lifting tool 5, and a core guide 6.
The containment 1 is a steel container with two-stage flanges, namely a top overhaul flange and a middle reloading flange, the reloading flange divides the containment 1 into an upper containment and a lower containment, the top of the upper containment is provided with the overhaul flange, the reloading flange and the overhaul flange form a two-stage open-top structure, when reloading is carried out, the overhaul flange at the top of the containment 1 is disassembled firstly to realize the first-stage open-top of the containment, and then the containment reloading flange is disassembled to realize the second-stage open-top of the containment.
The reactor pressure vessel 2 is a pressure vessel with a refueling flange and an internal component connection, wherein the refueling flange divides the reactor pressure vessel into an upper reactor pressure vessel and a lower reactor pressure vessel; the control rod driving mechanism, the upper in-pile member and the in-pile measuring grid are arranged in the upper reactor pressure vessel to form an integrated upper reactor pressure vessel.
The upper containment and the upper pressure vessel form an integral structure through the internal connecting rod structure fixed in advance, and an integral upper hoisting structure 3 is formed, so that an integral cover can be opened during material changing, namely, after the containment and the reactor pressure vessel are disassembled, the integral upper hoisting structure is used for hoisting once.
The lower reactor pressure vessel is internally provided with a core lifting structure 4, a core lifting appliance 5 and a core guiding device 6:
the core lifting structure 4 includes a structure for supporting the core assembly and for performing integral lifting, and the lifting interface flange is located at a deep core position 13m below the flange face of the reactor pressure vessel. The reactor core lifting structure can be separated from the lower reactor internals during material changing, and can bear all reactor core components for integral lifting, so that integral lifting and integral storage are realized.
The reactor core lifting device 5 is a lifting device structure body with an integral frame and comprising an operation platform and lifting tools, and is used for realizing integral lifting of the reactor core, and the lower end part of the lifting device can be connected with a reactor core lifting structure for integral lifting of the reactor core;
The core lifting structure 4 and the core lifting device 5 are connected in the following manner: the reactor core lifting appliance is provided with 3 sets of lifting columns, the whole reactor core structure is provided with 3 sets of lifting blocks, and the 3 sets of lifting columns are operated on the operation platform through operation tools so as to be respectively meshed with the corresponding lifting blocks.
The reactor core guiding device 6 comprises two-stage guiding consisting of an outer reactor guiding device and an inner reactor guiding device, and is used for centering and guiding the reactor core lifting appliance and the reactor core lifting structure. The outer guide device is used for guiding and pairing two outer guide posts outside the reactor pressure vessel and two guide sleeves at the upper end of the reactor core lifting appliance, and the inner guide device is used for guiding and pairing two guide grooves at the inner wall of the reactor core lifting appliance of the lower inner reactor component and two guide blocks at the lower end of the reactor core lifting appliance.
Example 2
As shown in fig. 3 and 4, there is provided an integrated reactor refueling system including the integrated reactor refueling apparatus of embodiment 1, and further including an integrated refueling machine 7, a reactor cavity water gate 8, a spent pool water gate 9, an integrated upper hoisting structure storage rack 10, a core hoisting structure storage rack 11, a lower internals storage rack 12, a spent fuel storage rack 13, and a refueling operation hall bridge 14.
The integrated refueling machine 7 is a bridge crane with telescoping sleeves and fuel assemblies and an inner insert dedicated operating gripper for replacing the fuel assemblies and inner inserts in the off-stack and spent areas.
The pile cavity sluice gate 8 is an automatic sluice gate with a restarting sealing ring and a movable switch executing mechanism and is used for isolating the pile cavity and a material-changing water pool.
The spent pool water gate 9 is an automatic water gate with a restarting sealing ring and a flat-open type switch executing mechanism, and is used for isolating a refueling water pool and a spent fuel water pool for spent fuel storage and plug-in switching.
The integrated upper hoisting structure storage rack 10 is a special storage rack structure with a supporting ring and a guide pin and is used for storing the uncapped integrated upper hoisting structure in a material changing pool.
The integrated upper hoist structure storage rack 10, which in this embodiment is a dedicated storage rack structure with support rings and guide pins, is used to store the uncapped integrated upper hoist structure in a refueling pool.
The core lifting structure storage rack 11 is a special storage rack structure with a support ring and guide pins, is used for storing the core lifting structure of the discharged reactor in a refueling water tank, and supports the integrated refueling machine 7 to operate a single fuel assembly.
The lower internals storage rack 12 is a dedicated storage rack structure with support rings and guide pins for storing the lower internals after the core lifting structure has been discharged in the refueling water basin.
The spent fuel storage grillwork 13 is a frame structure consisting of a plurality of rows and columns of dedicated fuel assembly storage chambers for storing fuel assemblies discharged from the core and fuel assemblies to be loaded into the core.
The hall bridge crane 14 is a heavy-load double-beam bridge crane with higher positioning accuracy and is used for hoisting heavy-load items through a special lifting appliance during reactor loading and unloading.
Example 3
As shown in fig. 5 to 12, an integrated reactor refueling process is provided, which is implemented using the integrated reactor refueling system of embodiment 2, comprising the steps of:
(1) Carrying out two-stage topping on the integrated reactor loading and reloading device to realize integrated uncovering, integrally removing the integrated upper hoisting structure, and placing the integrated upper hoisting structure on a storage rack of the integrated upper hoisting structure;
The specific process of two-stage topping is as follows: preparing before opening the roof, and removing the pile-roof penetrating piece; then carrying out first-stage roof opening of the containment, namely dismantling a maintenance flange of the containment, and the completed state is shown in fig. 5; then, disassembling the reactor pressure vessel flange, tripping a control rod driving mechanism in the containment by a special tool, lifting the in-pile measurement grid in the containment by the special tool, and disassembling the reactor pressure vessel flange in the containment by a bolt stretcher, wherein the conditions of opening the containment flange and integrally removing the integral upper hoisting structure are provided; finally, the second-stage opening of the containment, namely the disassembly of the containment refueling flange, is performed, so that the integrated uncovering is realized, as shown in fig. 6.
The integrated upper hoisting structure is integrally removed from the reactor by using the hall bridge crane for material changing operation and is placed on the storage rack of the integrated upper hoisting structure, and corresponding disassembly inspection and other on-site operations can be performed synchronously and subsequently, as shown in fig. 7.
(2) The reactor core lifting device is used for integrally lifting the reactor core lifting structure and is placed on a reactor core lifting structure storage rack;
The concrete process of integral hoisting of the reactor core hoisting structure is as follows: as shown in fig. 8 and 9, the lifting appliance before lifting the whole reactor core descends and centers, and a first-stage guiding stage, namely an off-pile guiding stage, is performed firstly, during the off-pile guiding process, the water level of the material change is synchronously lowered while the reactor core lifting appliance descends until the water level is close to the flange surface of the reactor pressure vessel, the water level is always kept slightly lower than the operating platform of the reactor core lifting appliance in the process, and the guiding pairing of the second-stage guiding stage is already realized in the transition section before the first-stage guiding stage is finished; and (3) continuing to center the lifting appliance before the integral lifting of the reactor core, and performing a second-stage guiding stage, namely an in-pile guiding stage, wherein the water level of the reloading is always kept slightly higher than the flange surface of the pressure vessel of the reactor but lower than the operating platform of the lifting appliance of the reactor core in the second-stage guiding, namely the in-pile guiding process.
As shown in fig. 10, after the centering is completed, an operator performs the centering on the operation platform through a remote connecting rod, so that the engagement of the hanger and the interface of the reactor core lifting structure is realized, the loaded lifting is started, the integral lifting of the reactor core is performed, the butt joint and the removal of the integral lifting of the reactor core are performed, and the lifting is placed on the reactor core storage rack.
Further, the hoist interface flange of the core hoist structure is positioned at a deep core position below the flange face of the reactor pressure vessel.
Further, all the two-stage reactor core guiding is completed, the whole reactor core structure is lifted to the reactor core storage rack, and the reloading water level is restored to the high normal water level at the moment, as shown in fig. 11.
(3) Carrying out off-pile refueling on the reactor by using an integrated refueling machine;
The specific process of external material changing is as follows: the operation of the fuel assemblies in the reactor core is performed by using the integrated refueling machine until the replacement of all the fuel assemblies in the whole reactor core is completed, and the operations of the replacement transfer of the single fuel assemblies, the replacement of the inserts and the like during the refueling process outside the reactor core can be stored by using the spent fuel storage grillwork positioned in the spent fuel pool, as shown in fig. 12.
(4) And (5) reloading the reactor with the reloaded reactor according to the reverse steps of the steps.
The above description is only of the preferred embodiments of the present invention and is not intended to limit the present invention, but various modifications and variations can be made to the present invention by those skilled in the art. Any modification, equivalent replacement, improvement, etc. made within the spirit and principle of the present invention should be included in the protection scope of the present invention.
Claims (7)
1. An integrated reactor pack refueling device, comprising:
the safety shell is provided with a material changing flange, the material changing flange divides the safety shell into an upper safety shell and a lower safety shell, and the top of the upper safety shell is provided with an overhaul flange;
The reactor pressure vessel is provided with a refueling flange which divides the reactor pressure vessel into an upper reactor pressure vessel and a lower reactor pressure vessel;
The upper containment vessel and the upper pressure vessel are of an integrated structure, and an integrated upper hoisting structure is formed.
2. The integrated reactor charge transfer apparatus of claim 1 wherein the charge transfer flange and service flange comprise a two-stage open top structure.
3. The integrated reactor refueling apparatus as recited in claim 1, wherein the upper reactor pressure vessel is provided with a control rod drive mechanism, upper internals and an in-stack measurement grid therein to form an integrated upper reactor pressure vessel.
4. The integrated reactor refueling apparatus as recited in claim 1, wherein the interior of the lower reactor pressure vessel is provided with a core lifting structure, a core lifting means and a core guiding means, the lower end of the core lifting means being connected to the core lifting structure.
5. The integrated reactor refueling device as recited in claim 4, wherein the core guide includes an out-of-core guide and an in-core guide.
6. An integrated reactor refueling system comprising the integrated reactor refueling system as recited in any one of claims 1-5, further comprising: the integrated refueling machine, a reactor cavity sluice gate, a spent pool sluice gate, an integrated upper hoisting structure storage rack, a reactor core hoisting structure storage rack, a spent fuel storage grid and a refueling operation hall bridge crane;
The integrated refueling machine is a bridge crane with a telescopic sleeve, a fuel assembly and an operation gripping apparatus special for the inner insert, and is used for replacing the fuel assembly and the inner insert in the out-of-pile and spent pool areas;
the pile cavity sluice gate is an automatic sluice gate with a restarting sealing ring and a movable switch executing mechanism and is used for isolating a pile cavity and a material changing water tank;
the spent pool sluice gate is an automatic sluice gate with a restarting sealing ring and a flat-open type switch executing mechanism and is used for isolating a refueling water pool and a spent fuel water pool.
7. An integrated reactor refueling process implemented by the integrated reactor refueling system as recited in claim 6, comprising the steps of:
carrying out two-stage topping on the integrated reactor loading and reloading device to realize integrated uncovering, integrally removing the integrated upper hoisting structure, and placing the integrated upper hoisting structure on a storage rack of the integrated upper hoisting structure;
the reactor core lifting device is used for integrally lifting the reactor core lifting structure and is placed on a reactor core lifting structure storage rack;
carrying out off-pile refueling on the reactor by using an integrated refueling machine;
and (5) reloading the reactor with the reloaded reactor according to the reverse steps of the steps.
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| CN202210939550.4A CN115376713B (en) | 2022-08-05 | 2022-08-05 | Integrated reactor loading and reloading device, system and process |
| PCT/CN2022/142739 WO2024027092A1 (en) | 2022-08-05 | 2022-12-28 | Integrated reactor, and charging and refueling system and method |
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| CN202210939550.4A CN115376713B (en) | 2022-08-05 | 2022-08-05 | Integrated reactor loading and reloading device, system and process |
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| CN115376713B (en) * | 2022-08-05 | 2024-06-14 | 上海核工程研究设计院股份有限公司 | Integrated reactor loading and reloading device, system and process |
| CN116705374A (en) * | 2023-06-19 | 2023-09-05 | 国科中子能(青岛)研究院有限公司 | reactor |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103489488A (en) * | 2012-06-11 | 2014-01-01 | 中国核动力研究设计院 | Module type pressurized water reactor |
| CN105719710A (en) * | 2014-12-01 | 2016-06-29 | 上海核工程研究设计院 | Small modular reactor fuel handling and refueling system |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| DE1812088C3 (en) * | 1968-12-02 | 1979-11-29 | Interatom Internationale Atomreaktorbau Gmbh, 5060 Bergisch Gladbach | Device for changing fuel elements of a non-stationary nuclear reactor |
| JP2002122686A (en) * | 2000-10-17 | 2002-04-26 | Toshiba Corp | Boiling water nuclear power plant and its construction method |
| JP2007010457A (en) * | 2005-06-30 | 2007-01-18 | Toshiba Corp | Reactor containment vessel and boiling water nuclear plant |
| CN103440884B (en) * | 2013-08-12 | 2016-05-11 | 中国核动力研究设计院 | Be placed in the application process of the steam pressure stabilizer of reactor pressure vessel inside |
| CN106653123B (en) * | 2015-11-02 | 2019-01-22 | 中广核研究院有限公司 | A kind of material-changing method and material-changing device for land Small reactor |
| US10818403B2 (en) * | 2016-03-29 | 2020-10-27 | Nuscale Power, Llc | Inter-module fuel shuffling |
| CN106910541A (en) * | 2017-03-30 | 2017-06-30 | 上海核工程研究设计院 | A kind of close-coupled nuclear reaction stows technique of reloading |
| CA3064304A1 (en) * | 2017-05-22 | 2018-11-29 | Claudio Filippone | Nuclear power generator, fuel cartridges for nuclear power generator, and related methods |
| CN108648837B (en) * | 2018-05-15 | 2020-08-11 | 中国核动力研究设计院 | Full natural circulation modular small reactor |
| CN110164572A (en) * | 2019-05-09 | 2019-08-23 | 上海核工程研究设计院有限公司 | A kind of compact reactor refuling device that whole reactor reloading pattern can be achieved |
| CN115376713B (en) * | 2022-08-05 | 2024-06-14 | 上海核工程研究设计院股份有限公司 | Integrated reactor loading and reloading device, system and process |
-
2022
- 2022-08-05 CN CN202210939550.4A patent/CN115376713B/en active Active
- 2022-12-28 WO PCT/CN2022/142739 patent/WO2024027092A1/en not_active Ceased
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103489488A (en) * | 2012-06-11 | 2014-01-01 | 中国核动力研究设计院 | Module type pressurized water reactor |
| CN105719710A (en) * | 2014-12-01 | 2016-06-29 | 上海核工程研究设计院 | Small modular reactor fuel handling and refueling system |
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| Publication number | Publication date |
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| WO2024027092A1 (en) | 2024-02-08 |
| CN115376713A (en) | 2022-11-22 |
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